Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 216
... Burnup Credit ( 4 ) . These are the fissile and fissionable nuclides ; urani- um 235 , 236 , and 238 , and plutonium 239 , 240 and 241. The major fission products are also listed , these are ; " Mo , " Tc , 11Ru , 103Rh , 109 Ag , 133Cs ...
... Burnup Credit ( 4 ) . These are the fissile and fissionable nuclides ; urani- um 235 , 236 , and 238 , and plutonium 239 , 240 and 241. The major fission products are also listed , these are ; " Mo , " Tc , 11Ru , 103Rh , 109 Ag , 133Cs ...
Page 219
... burnup . Although its drawback is that it can be used only on fuel cooled to a maximum of 8 or 9 years . The most useful burnup indicator for fuel with a broad range of burnup and cooling times ( to more than 50 years ) is therefore the ...
... burnup . Although its drawback is that it can be used only on fuel cooled to a maximum of 8 or 9 years . The most useful burnup indicator for fuel with a broad range of burnup and cooling times ( to more than 50 years ) is therefore the ...
Page 220
... burnup ( MWd / Te ( U ) ) . Passive Neutron Measurements The passive neutron count rate from the fuel plotted against the local declared burnup is shown in Fig . 4. As indicated there is some dependence on initial enrichment . The ...
... burnup ( MWd / Te ( U ) ) . Passive Neutron Measurements The passive neutron count rate from the fuel plotted against the local declared burnup is shown in Fig . 4. As indicated there is some dependence on initial enrichment . The ...
Contents
DESCRIPTIONS OF NATIONAL ENVIRONMENTAL MANAGEMENT PROGRAMS | 1 |
A Service to National Community in Chile | 11 |
Cora Project The Italian Way for Conditioning High and Low Level Liquid Radioactive Wastes | 23 |
Copyright | |
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acid actinides activity analysis assessment backfill bentonite borehole brine burnup calculated canister carbon CCDF cell cement cesium chemical coefficient compaction composition concentration containing criteria decommissioning decontamination disposal facility dose drums effect Energy environment environmental evaluation extraction flow geological glass groundwater hydraulic IAEA incineration ion exchange ion exchange resins level waste material measured ment neptunium Nirex nitric acid nuclear fuel nuclear power nuclides operation organic oxidation parameters performance permeability phase plant plutonium polonium potential production radiation radioactive contamination Radioactive Waste Management radionuclides radwaste reactor reduce release repository reprocessing resins risk rock safety salt samples scenarios Sellafield simulated solid solution sorbent sorption specific spent fuel storage surface Table tank technetium temperature tests tion transport treatment uranium vitrification volume waste disposal waste form waste management waste packages WIPP zirconolite zone